ASME QME 1 : 2017
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES
Hardcopy , PDF
03-06-2023
English
23-08-2017
Foreword
Committee Roster
Organizaton of QME-1
Summary of Changes
Section QR - General Requirements
Mandatory Appendix to Section QR
QR-I - Qualification and Duties of Registered
Professional Engineers for Certification Activities
Nonmandatory Appendices to Section QR
QR-A - Seismic Qualification of Active
Mechanical Equipment
Appendix QR-A - Tables
QR-B - Guide for Qualification of Nonmetallic Parts
QR-C - Sample Registered Professional Engneer
Certification Statements
Appendix QR-C Forms
Section QDR - Qualification of Dynamic Restraints
Mandatory Appendix to Section QDR
QDR-I - Qualification Specification for Dynamic Restraints
Nonmandatory Appendices to Section QDR
QDR-A - Restraint Similarity
QDR-B - Typical Values of Restraint Functional Parameters
Section QP - Qualification of Active Pump Assemblies
Mandatory Appendix to Section QP
QP-I - Qualification Specification for Active Pump Assemblies
Nonmandatory appendices to Section QP
AP-D - Pump Similarity Checklist
QP-E - Guidelines for Shaft-Seal System Material and
Design Consideration
Appendix QP-E Tables
Section QV - Qualification Requirements for Active Valve
Assemblies for Nuclear
Section QV Table
Mandatory Appendix to Section QV
QV-I - Qualification Specification for Active Valves
Nonmandatory Appendix to Section QV
QV-B - Static Side Load Testing for Power-Actuated
and Relief Valve Assemblies
Section QVG - Guide to Section QV: Determination of
Valve Assembly Performance Characteristics
Gives he requirements and guidelines for the qualification of active mechanical equipment whose function is required to ensure the safe operation or safe shutdown of a nuclear facility.
DocumentType |
Standard
|
ISBN |
978-0-7918-7155-3
|
Pages |
128
|
PublisherName |
American Society of Mechanical Engineers
|
Status |
Superseded
|
SupersededBy | |
Supersedes |
IEEE 382-2006 | IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations |
HI 1.6 : 2000 | CENTRIFUGAL PUMP TESTS |
HI 1.1-1.5 : 1994 | CENTRIFUGAL PUMPS - NOMENCLATURE, DEFINITIONS, APPLICATIONS AND OPERATION |
API 682 : 2014 | PUMPS - SHAFT SEALING SYSTEMS FOR CENTRIFUGAL AND ROTARY PUMPS |
ASCE 4 98 : 2000 | SEISMIC ANALYSIS OF SAFETY-RELATED NUCLEAR STRUCTURES AND COMMENTARY |
HI 9.1 - 9.5 : 2015 | PUMPS - GENERAL GUIDELINES |
IEEE 334 : 2007 | QUALIFYING CONTINUOUS DUTY CLASS 1E MOTORS FOR NUCLEAR POWER GENERATING STATIONS |
IEEE 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
ANS 51.1-1983(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
IEEE 101 : 1987 | GUIDE FOR THE STATISTICAL ANALYSIS OF THERMAL LIFE TEST DATA |
ASME OM : 2017 | OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS |
ANS 52.1-83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS |
IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
ASME PTC8.2 : 1990 | PERFORMANCE TEST CODES - CENTRIFUGAL PUMPS |
IEEE 627-2010 | IEEE Standard for Qualification of Equipment Used in Nuclear Facilities |
ASME B73.1 : 2012 | SPECIFICATION FOR HORIZONTAL END SUCTION CENTRIFUGAL PUMPS FOR CHEMICAL PROCESS |
ASME PV CODE 3 APP DIV 1 : 2017 | BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - APPENDICES |
ASME B73.2 : 2016 | Specification for Vertical In-Line Centrifugal Pumps for Chemical Process |
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